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Category:Letter
MONTHYEARML24268A3382024-10-16016 October 2024 Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing IR 05000220/20243022024-10-0303 October 2024 Initial Operator Licensing Examination Report 05000220/2024302 NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024 Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000220/20240052024-08-29029 August 2024 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005) IR 05000220/20240102024-08-22022 August 2024 Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024 Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 ML24215A3002024-08-0202 August 2024 Operator Licensing Examination Approval ML24213A1412024-07-31031 July 2024 Requalification Program Inspection NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024 Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations ML24198A0852024-07-16016 July 2024 Senior Reactor and Reactor Operator Initial License Examinations RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2 ML24158A2052024-05-15015 May 2024 Annual Radioactive Environmental Operating Report IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds NMP2L2880, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024 Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024 2023 Annual Environmental Operating Report NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24074A2812024-03-14014 March 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable IR 05000220/20230062024-02-28028 February 2024 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006) NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024 Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 2024-09-04
[Table view] Category:Licensee Event Report (LER)
MONTHYEARNMP2L2880, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024 Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024 Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater ML18018B1152018-01-18018 January 2018 Scram Summary 91-01 Relating to a Turbine Trip and Automatic Reactor Scram When the Main Transformer Phase B Developed an Internal Fault on August 13, 1991 ML18018B1122018-01-18018 January 2018 Scram Summary 91-01 Relating to an Event on August 13, 1991 Concerning a Turbine Trip and Automatic Reactor Scram When the Main Transformer Phase B Developed an Internal Fault 05000410/LER-2017-0022017-11-28028 November 2017 Secondary Containment Inoperable Due to Wind Conditions, LER 17-002-00 for Nine Mile Point Nuclear Station, Unit 2 Regarding Secondary Containment Inoperable Due to Wind Conditions 05000220/LER-2017-0032017-11-0202 November 2017 Automatic Reactor Scram due to Reactor Vessel Low Water Level, LER 17-003-00 for Nine Mile Point, Unit 1, Regarding Automatic Reactor Scram due to Reactor Vessel Low Water Level 05000410/LER-2017-0012017-10-0404 October 2017 1 OF 5, LER 17-001-00 for Nine Mile Point Nuclear Station, Unit 2, Regarding Automatic Reactor Scram due to High Reactor Pressure 05000220/LER-2017-0022017-05-18018 May 2017 Manual Reactor Scram Due to Pressure Oscillations, LER 17-002-00 for Nine Mile Point Nuclear Station, Unit 1 Regarding Manual Reactor Scram Due to Pressure Oscillations NMP1L3129, LER 17-01-00 for Nine Mile Point Unit 1 Manual Reactor Scram Due to High Turbine Vibration2017-02-0808 February 2017 LER 17-01-00 for Nine Mile Point Unit 1 Manual Reactor Scram Due to High Turbine Vibration 05000220/LER-2017-0012017-02-0808 February 2017 Manual Reactor Scram Due to Hiah Turbine Vibration, LER 17-01-00 for Nine Mile Point Unit 1 RE: Manual Reactor Scram Due to High Turbine Vibration 05000220/LER-2016-0022016-09-26026 September 2016 Isolation of both Emergency Condensers due to loss of UPS 162B, LER 16-002-00 for Nine Mile Point, Unit 1, Regarding Isolation of Both Emergency Condensers due to Loss of UPS 1628 05000220/LER-2016-0012016-07-12012 July 2016 Secondary Containment Inoperable Due to Simultaneous Opening of Airlock Doors, LER 16-001-00 for Nine Mile Point Nuclear Station Unit 1 Regarding Secondary Containment Inoperable Due to Simultaneous Opening of Airlock Doors 05000410/LER-2016-0012016-06-0606 June 2016 Secondary Containment Inoperable Due to Simultaneous Opening of Airlock Doors, LER 16-001-00 for Nine Mile Point, Unit 2, Regarding Secondary Containment Inoperable Due to Simultaneous Opening of Airlock Doors 05000410/LER-2015-0032016-03-31031 March 2016 Primary Containment Isolation Function for some valves not maintained during Surveillance Testing, LER 15-003-01 for Nine Mile Point, Unit 2, Regarding Primary Containment Isolation Function For Some Valves Not Maintained During Surveillance Testing ML1005504842010-02-15015 February 2010 Special Report: Inoperable Suppression Chamber Water Level Instrumentation ML0903605172009-01-21021 January 2009 Special Report: Inoperable Channel of Suppression Chamber Water Level Instrumentation ML0534802052005-12-0202 December 2005 Special Report for Nine Mile Point Unit 1 Re Channel #12 of the Containment Hydrogen Monitoring System Inoperable ML0515400362005-05-24024 May 2005 Special Report, Channel #11 of the Containment Hydrogen Monitoring Inoperable for Scheduled Preventive Maintenance ML0509602522004-12-17017 December 2004 Final Precursor Analysis - NMP-2 Grid Loop ML0509602422004-12-17017 December 2004 Final Precursor Analysis - NMP-1 Grid Loop ML0434304492004-11-22022 November 2004 Special Report for Nine Mile Point, Unit 1 Regarding Channel #12 of the Containment Hydrogen Monitoring System Removed from Service for Planned Maintenance ML0425300732004-08-27027 August 2004 Special Report for Nine Mile Point Unit 1 Re Channel #11 of the Containment Hydrogen Monitoring System Inoperable for Scheduled Preventive Maintenance ML0418105152004-06-18018 June 2004 Revised Special Report for Nine Mile Point, Unit 1 Re Channel #12 of the Containment Hydrogen Monitoring System Inoperable ML0413204992004-05-0404 May 2004 Special Report for Nine Mile Point Unit 1 Regarding Inoperability of Channel #12 of the Containment Hydrogen Monitoring System ML0410603992004-04-0707 April 2004 Special Report, Channel #11 of the Containment Hydrogen Monitoring System Inoperable for Scheduled Corrective Maintenance ML0336404932003-12-19019 December 2003 Special Report Regarding Channel #11 Containment Hydrogen Monitoring System Being Inoperable for Scheduled Preventive Maintenance ML0221303572002-07-23023 July 2002 Special Report for Nine Mile Point Unit 2 Re Noble Gas Activity Monitoring Instrumentation Inoperable for Greater than 72 Hours ML18018B1112000-03-0707 March 2000 LER 99-019-01 Supplement 1, for Nine Mile Point, Unit 2, Regarding Two Standby Liquid Control Valves Not Tested as Required by Technical Specification 4.0.5 and LER 99-010-01, Supplement 1, Unit 2 Reactor Trip Due to a Feedwater Master .. ML18018B0771997-12-29029 December 1997 Letter Replying to Notice of Violation as Contained in NRC Inspection Report 50-220/97-07 and 50-410/97-07 ML18018B1171991-09-0404 September 1991 NRC UPS Meeting ML18018B2511978-09-29029 September 1978 LER 78-034-00 for Nine Mile Point, Unit 2, Regarding an Environmental Contractor Obtaining 22 Hourly Fish Impingement Samples, and One Two-Hour Sample, Which Is Contrary to the Technical Specification Requiring 24 Hourly Samples ML18018B2521978-08-24024 August 1978 LER 78-030-00, 78-031-00, and 78-032-00 for Nine Mile Point Unit 1 Regarding, Respectively, Unavailability of Feedwater Pump 29-03 While Its Pump Seals Were Replaced, Unavailability of Liquid Poison Pump NP02A While a Frozen Valve .. ML18018B2531978-07-28028 July 1978 LER 78-029-00 for Nine Mile Point, Unit 2, Regarding Discovery of High Drywell Pressure Switches RE04A, RE04B, and RE04C with Setpoints Less Conservative than the Technical Specifications ML18018B2541978-07-25025 July 1978 LER 78-028-00 for Nine Mile Point Unit 1 Regarding Discovery of the Allowable Test Interval of TS 4.1.4c for the Core Spray Power-Operated Valves Had Been Exceeded ML18018B2551978-07-13013 July 1978 LERs 78-025-00, 78-026-00, and 78-027-00 for Nine Mile Point Unit 1 Regarding, Respectively, Discovery of RE04D with a Setpoint of 3.70 PSIG, Discovery of Numerous Small Leaks in Small Sample and Instrument Pipes, and Discovery of RE22D wit ML18018B2561978-06-21021 June 1978 LER 78-024-00 for Nine Mile Point Unit 1 Regarding Discovery That Test N1-St-Q2,4,5,7,8,9, and 10 Had Not Been Performed During a Review of Quarterly Surveillance Test Results ML18018B2571978-06-12012 June 1978 LERs 78-020-00, 78-021-00, 78-022-00, and 78-023-00 for Nine Mile Point Unit 1 Regarding, Respectively, Discovery of RE18A with a Setpoint of 135 Inches Wc, Discovery of RE04A and RE04B with a Setpoint of 3.65 PSIG, Discovery of Turbine ... ML18018B2591978-06-0101 June 1978 LER 78-019-00 for Nine Mile Point Unit 1 Regarding Discovery That Hydraulic Snubber 31-HS-1 Had Failed and Was Empty of Hydraulic Fluid and Disconnected from Its Anchor at the Feedwater Pipe ML18018B2581978-05-26026 May 1978 LER 78-009-01 for Nine Mile Point Unit 1 Regarding Replacement of Explosive Charges in the TIP Shear Valves with New Charges and the Resulting Unsatisfactory Ohmmeter Continuity Test for Acceptable Electric Contact ML18018B2601978-04-24024 April 1978 LER 78-018-00 for Nine Mile Point Unit 1 Regarding Discovery of Main Steam High Flow Switch with a Setpoint of 106.2 PSI, Which Is Above the Technical Specification ML18018B2611978-04-0707 April 1978 LERs 78-014,00, 78-016-00, and 78-016-00 for Nine Mile Point Unit 1 Regarding, Respectively, Discovery That the Fuel Transfer Pump on 102 D/G Would Not Fill the Day Tank, Discovery of RE18C with a Setpoint of 129 Inches Wc, and RE04B .. ML18018B2621978-03-28028 March 1978 LER 78-014-00 and LER 78-015-00 for Nine Mile Point Unit 1 Regarding, Respectively, Discovery That the Fuel Transfer Pump in 102 D/G Would Not Fill the Day Tank and Discovery That #12 Control Room Air Treatment Fan Would Not Run ML18018B2631978-03-16016 March 1978 LER 78-011-00, LER 78-012-00 and LER 78-013-00 for Nine Mile Point, Unit 1 Re Technical Specification Violations of Section 3.6.2 ML18018B2641978-03-0101 March 1978 LER 78-007-00, LER 78-008-00, LER 78-009-00 and LER 78-010-00 for Nine Mile Point, Unit 1 Re Technical Specification Violations of Listed Sections ML18018B2651978-02-24024 February 1978 LER 78-006-00 for Nine Mile Point, Unit 1 Re During Steady State Operation, Performance of Surveillance Test IC-75 Found a Trip Setpoint of 22.5 Inches Water on One Vacuum Switch in the Vacuum Relief System from the Pressure Suppression Cha ML18018B2661978-02-0707 February 1978 LER 78-004-00 and LER 78-005-00 for Nine Mile Point, Unit 1 Re During Unit Shutdown, Reserve Power Breaker on Power Board II Failed to Close in After Loss of Normal Power and During Plant Outage While Marking Up Outside MSIV 01-03 Discovere ML18094A0301978-01-31031 January 1978 LER 1978-003-03 for Nine Mile Point Unit 1 Re Surveillance Test Found Main Steam High Flow Switch with Setpoint of 107.5 PSI ML18018B1221978-01-31031 January 1978 LER 78-002-00 for Nine Mile Point 1 Regarding Drywell High Pressure Switch RE04A Setpoint Drift and LER 78-003-00 ML18094A0291978-01-13013 January 1978 LER 1978-001-00 for Nine Mile Point Station Unit 1 Re Delta Temperature of Discharge Water Exceeded Specification 2.1.5 of Environmental Tech Specs ML18018B2701978-01-13013 January 1978 Submittal of Licensee Event Report LER 78-01 Concerning Delta Temperature of the Discharge Water Exceeded Environmental Tech. Spec 2024-05-01
[Table view] |
Text
r /u(y,y REGULATORY INFORMATION DISTRIBUTIGN SYSTEM (RIDS DISTRIBUTION FOR INCOMING MATERIAL 50-220 REC: GRIER B H ORG: SCHNEIDER R R DOCDATE: 05/26/78 NRC NIAGARA MOHAWK PWR DATE RCVD: 06/07/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR i ENCL 1 FORWARDING LICENSEE EVENT REPT (RO 50-220/78-009) ON 02/2i/78 CONCERNING TIP SHEAR VALVES REPLACED WITH NEW CHARGES'HOWED OHMMETER CONTINUITY TEST FOR ACCEPTABLE ELEC CONTACT WAS UNSATISFACTORY... W/ATT.
PLANT NAME: NINE MILE PT, UNIT i REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:P~
++4HI+4~++++4F+++4++ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS
< DISTRIBUTION CODE A002)
FOR ACTION: BR~HIE ORBN3 BC~~W/4 ENCL INTERNAL: REG F IL fENCL
++W/2 ENCL NRC PDR+<W/ENCL MIPC++W/3 ENCL I 5 C SYSTEMS BR4<W/ENCL EMERGENCY PLAN BR44W/ENCL NOVAK/CHECK++W/ENCL EEB4 4W/ENCL AD FOR ENG+4W/ENCL PLANT SYSTEMS BR<+W/ENCL HANAUER+>W/ENCL AD FOR PLANT SYSTEMS+>W/ENCL AD FOR OPER TECH4+W/ENCL REACTOR SAFETY BR+<W/ENCL ENGINEERING BRw+W/ENCL VOLLMER/BUNCH+4W/ENCL KREGER/ J. COLLINS++W/ENCL POWER SYS BR++W/ENCL K SEYFRIT/IE+wW/ENCL EXTERNAL: LPDR S OSWEGO'Y44tW/ENCL T IC%+W/ENCL NSIC44W/ ENCL ACRS CAT B++W/i6 ENCL COPIES NOT SUBiJITTED PER REGULATORY'UIDE 10 F 1 DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR 78i600~24 SIZE: iP l.iP+2P
It I "I NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE, N.Y. 13202/TELEPHONE (315) 474-1511 Wage 26, 1978 C
A,. Boyee, H. G/ci.E/L Nrcecto/L I,,)
Ueu."ed Statue Much ea/L Regulato/Ly CommQ dion ~CO Reg4.on I CAq)
Vl C Al 631 Pa/ck Avenue, Kmg o( P/curiam, PA. 19406
( CV C3 Pll RE: Pock& Mo. 50-220 Sea/L hh,. G/ci.E/LI In acco/cdance eke M~nc hKLc Poi1< Nucjea/c. S~on Urbe >1 T'cchrucat'. Speci.pcatLon5, cd he/ceby subvert Licensee. Event Repo/Lt LER 78-09 tRev~ion 1), c0&eh c0as p/Lev~oasZg submitted on hfa/cch 1, 1978.
TRQ /cepo/Lt cd completed in Xhe, )o/cmat designated an MUREG-0161, dated July 1977.
Velcro Wul,g gou46, ORIGINAL SIGNED BY R.R. SCHNEIDER R.R. Schneiden, Vi,cc P~e5<dcnt-ELec,tcc.ie P/coducti.oII Eneloau/ce, (3 eopi.c5) xc: O~mt'o/c, 0)Pce o) 'ISE (30 cop~M) 8~ceto/I,, 0(tIice. o$ WIPC (3 copiu) 78g 6003'~
NRC FORM 3GG U. S. NUCLEAH HEUULA I UHY UUMMlbbIEIN
{7-771 LICENSEE EVENT REPOR CONTROL BLOCK:
I 6 Q [PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) ~
~01 N Y NM P 1 Q2 0 0 - 0 0 0 0 0 - 0 0Q34 I QRLLJ Qs 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 C.'1'8 Pp CON'T
~OP 7 8 soURGE LL lQB 0 5 0 0 0 2 2 Q7 EVFNT DATE 74 Q8 ~05 75 2 6 7 REPORT DATE 8
80 Qs 60 61 DOCKET NUMBER GS G9 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 Durin routine station o eration with the TIP detectors withdrawn ex-plosive charges in the TIP shear valves were re laced with new char es.
After re lacement, an ohmmeter continuit test for acce table electric
~OS contact'was unsatisfactory. The normal TIP isolation system was o er-
~os able at this time. An evaluation has shown that this condition could not
~0 "create. a otential for a safet hazard.
~OB 7- 8 80 SYSTEAI CAUSE CAUSE CONIP VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE
~OS ~XX Q44 ~GOER ~AQE Y A L Y E X QE ~XQE ~X g<,
7 8 9 10 11 12 13 18 19 20 SCOUENTIAL OCCURRENCE REPORT REVISION OPT LERIRO REPQRT ACTION .FUTURE EVENT YEAR
~78 21 22 EFFECT
~
23 SHUTDOWN 24 REPORT NO.
~00 9 26
~~
27
~01 ATTACHMENT 28 CODE 29 NPRDQ TYPE
~T 30
~
31 PRIME COMP.
ND.
~l 32 COMPONEI9T TAKEN ACTION ON PLANT METHOD HOURS +22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER 0 0 0 0 8 0 8 0
~NOPE ~ZOER 33 34
~ZQEO 35
~ZQEE 36 37 40 41 Y
On ~NOR 42 L~JOEE 43 44 47 Q
CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o It was found that the actual electrical connections as ori inall wired were not as described in the Maintenance Procedure or in a re-vised GE drawing. The wiring was chan ed to a ree with the revised GE..
dw . and all four of the old s uib devices were detonated successfull
~14 7 8 9 FACII.ITY STATUS AI POWER OTHER STATUS Q METHOD OF DISCOVERY DISCOVERY DESCRIPTION s E Q28 ~09 9 QEO Maintenance Procedure 7 8 9 10 12 44 45 4G 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITYQSS LOCATION OF RELEASE QB
~Z Q33 ~ZQ24 NA NA 7 8 9 10 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DCSCRIPTION Q30 T ~00 0 QET ~2Qas NA 7 8 9 'I1 12 13 80 PERSONNEL INJURIES 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACII.ITY TYPE DESCRIPTION Q43 0 Z Q42 NA 7
'I o
8 8
9 ISSUED
~NQ<<NA 9
10 PUBLICITY DESCRIPTION 10 Q PHONE'0 NRC USE ONLY 80 80 P
O.K. MacVittie 315-343-2110 X1558 0 NAME OF PREPARER , s7
NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE. N.Y. 13202/TELEPHONE (315) 474 ~ 1511 blate 26, 1978 htIL. Bogee H. G/u.e/z
%Aero/z U~ed S~eh Nucleate Regulato/zg CommQ a~on Regin I 631 Pa/zfz Avenue, King os P/uL56~, PA. 19406 RE: Goclz& hlo. 50-220 LER 78-09/01T-1 one hLile Po~et NucLea/L Staf;ion UI~ <1 17eatL hk. Gru.e/L:
G~g /zozLtine a~on opercation wMh Che TIP d&ectom eLthd/zawn, explosive cha/zgu ~n Che TIP System ahea/L vaEvas we/ze rzeplaced eke neIv eha/zgu. The, explosive ope/Iated TIP ahea/LLeo~on vaEve5 a/ze a bactz-up ayhkem Co be used )o/LLsolatLon o( Che TIP Whee ~n Che eveILt ML6 noC possible W ~hd/Law .the, detecto/L ao Che no/ImaL automatic volation agkeIn may (unct'.on.
FoLEoeu1g /zeplacement', pe/Lfoenanee og hfau<enance PnocedIg/Le Nl-Ih)P-TIP-3 (ound Chat Xhe ohmmete/L eo~nuktg wa6 unbatQ (aetna.
tnt fo/L acceptable eLeet/u.c compact The, norImaL TIP Wbe Lsofation aIgaiem wa5 ope/Iable at'ke ~e.
IC wm ltound Chat She a~ eLectIu.eaL connectioIa Co She exploa~ve chatzge5 we/ze nok a5 de5c/u.bed ~n Che h(aintenanee PtzoceduIze. Gene/zaE ELecttu.c NE'0 Paodu& Se/zvace wa5 znfo/Imed o( 4he p/zoblen and gL ven Che numb@@ of She cbuueinga rued Co Ice .the agkem. A /zevke~oIz Co the dIzalinga, wtw.eh had o/u'.g~aLEy been msued ~n Feb~g 1968, wa5 Located.
The, con)~gurzation ahoIvn ~n 4kB rzevmion would cause .tke, chcuzgas Co pJce.
The w~g (o/L pru,ng Xhe eha/zgm ~n Xhe TIP Sgs.teIn wa5 changed Co match Chat shown ~n She /Levied cbuueinga. ALE o( Che old cluvzge5 we/Le CmX +fred w~ng the /Levied w~iI1g scheme. TheIg aEL /vied success(uLQg.
Ad~onaLEg, Eke Pae-Ope/LationaL TmC of ou/z Liquid PoQ on SgakenI wa5 rzev~ewed Co a5szI/ze Chat She explosive cheat. vaEve5 kn .that atgateJn had been opetzationaELg Ce54ed p/u.o/L .t'o ata/Ltup.
In aden to XlIe u&u'.ng p/zoblem uncove/Led, Lt Iver@ (ound Chat Xke 2 AMP fme5 /zeqc&ced .uc Clue squib ~cuit've/zeiI+WILt bloIv dev~ce5 xrvkead o) Che slow blow Xgpe apeciPed bg She vendo/z. ALE o( Xhe (tun Nze moI/w'.to/L/coI~ol u~ we/Le /replaced wMh new dev~ce5,
Page 2 The. TIP SgaCen inde coetainntmt ~ deigned Joc 124 prig wiCh Che.
baLL valve closed. 8uni>ig a, Loath o J coolm< accident, coetaiiuneet pcuame lou been calculaCed Co <each 95 prig. Fox a poCeetiuk aaJeCy pxoblem Co exQC dkutiwg a LOCA, Che TIP paobe wouLd have Co JaiL in Che imbed position, Che, TIP ~~neet aheaCh would have, Co btceak and Che, TIP cheart.
vaLve would have Co JmX Co Jme, Chas preventing TIP Cube Leo~on. A aaJeCy evaLuaCion o J Cps concKtion hm determined Chat Che poCeetiaL Jo< a aaJeCy hazcvzd do@5 noC exQC.
Sincerely yocuu, ORIGINAL SIGNED BY R.R. SCHNEIDER R.R. Schneideft, Vice PamidenC-ELe~c PaoducCion